公开(公告)号：US08535636B1

公开(公告)日：2013-09-17

申请号：US13624744

申请日：2012-09-21

Applicant: Korea Atomic Energy Research Institute ,  Korea Hydro & Nuclear Power Co., Ltd.

Inventor： Hee Chul Eun ,  Yung Zun Cho ,  Hwan Seo Park ,  Tae Kyo Lee ,  In Tae Kim ,  Geun Il Park

IPC: C01F5/00

CPC classification number: G21C19/48 ,  C01D15/04 ,  C01F11/02 ,  C01F11/24 ,  G21F9/28 ,  G21F9/32 ,  Y02W30/884

Abstract: Disclosed herein is a method of separating group II nuclides from a radioactive waste lithium chloride salt and recovering renewable lithium chloride, comprising the steps of: injecting lithium oxide into a lithium chloride salt containing group II nuclides to convert the group II nuclides into thermally-stable oxide or oxychloride; and vaporizing and condensing the lithium chloride salt under a reduced pressure condition to separate the group II nuclides and recover recyclable lithium chloride. The method is advantageous in that group II nuclides existing in the form of chloride, which is not highly thermally-stable in a lithium chloride (LiCl) to salt and is not easily solidified, can be converted into oxides or oxychlorides, which is highly thermally-stable in the lithium chloride (LiCl) salt and is easily solidified, without producing impurities.

Abstract translation: 本文公开了一种从放射性废物氯化锂盐中分离II族核素并回收可再生氯化锂的方法，包括以下步骤：将锂氧化物注入含II族核素的氯化锂盐中，将II族核素转化为热稳定性 氧化物或氯氧化物; 并在减压条件下蒸发和冷凝氯化锂盐，以分离第二组核素，并回收可再循环的氯化锂。 该方法的优点在于以氯化锂（LiCl）对盐不高度热稳定并且不容易固化的以氯化物形式存在的II族核素可以转化为高度热的氧化物或氯氧化物 - 稳定在氯化锂（LiCl）盐中，并且容易固化，而不产生杂质。

公开(公告)号：US11810684B2

公开(公告)日：2023-11-07

申请号：US17410097

申请日：2021-08-24

Applicant: KOREA ATOMIC ENERGY RESEARCH INSTITUTE

Inventor： Ki Rak Lee ,  Hwan Seo Park ,  Geun Il Park ,  Hong Joo Ahn ,  Jung Hoon Choi ,  Hyun Woo Kang ,  In Tae Kim

IPC: G21F9/30 ,  B01D53/00 ,  B01D53/04 ,  G21F9/08 ,  G21F9/12

CPC classification number: G21F9/30 ,  B01D53/002 ,  B01D53/04 ,  G21F9/08 ,  G21F9/12 ,  B01D2253/10 ,  B01D2257/708 ,  B01D2259/40088

Abstract: The present invention relates to a method of separating and removing a radioactive nuclide, particularly, C-14 and tritium from a radioactive waste resin, and an equipment therefor. The method of treating a radioactive waste resin of the present invention includes recycling of condensate water from which a C-14 radionuclide in the condensate water is removed, into a treatment part for a radioactive waste resin.